ML19331D951
| ML19331D951 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/10/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19331D947 | List: |
| References | |
| 501-7-005, 501-7-5, NUDOCS 8009040391 | |
| Download: ML19331D951 (41) | |
Text
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501-7-005 August 10, 1980 Revision 0 FARLEY NUCLEAR PLANT A
UNIT 2 PHASE III TEST PRCCEDURE /Y 501-7-005 ,
9 FORCED CIRCULATION CCOLDOWN Approved: )
O_.
pit . weer Y
l Date Issued:
/
Diskette No. 6 8009340 % 3 9 1
I
. 501-7-005
, s
- ' \
l FARIEI NUCLEAR PLANT -;
- UNIT 2 !
.. PHASE III TEST PRCCEDURE 501-7-005 FORCED CIRCULATION CCOLDOWN 1.0 Purpose This procedure contains the information necessary to determine excore detector indicated power correction factors as a function of the average RCS cold leg temperature. These factors will be determined during a FORCED CIRCULATION COOLDOWN and subsequent heatup of the RCS with the reactor at approximately 3% power.
2.0 Initial Conditions 2.1 T is approximately 547*F. The Steam Dump
/ i$y8perating (or available) to maintain T"V" in the Steam Pressure Mode.
2.2 Pressurizer pressure is being maintained at
/ approximately 2235 psig by automatic operation
(._ of the Pressurizer Pressure Control System.
2.3 Pressuriser level is being maintained at
/ approximately 22% by automatic operation of the Pressurizar Level Control System.
2.4 The S/G's are being maintained at approxi-
/ mately 33%. The Main Feedwater or AFW System is operating (or available) to maintain S/G levels.
2.5 All three RCP's are running.
/
2.6 The CVCS is in a normal at-power lineup.
/ Sufficient makeup is available for a cooldown to approximately 500*F.
2.7 Both Shutdown Banks are fully withdrawn.
/
2.8 The reactor is critical at approximately
/- 3% power.
l l
1 Rev. O
501-7-005 CAUTION e
The PR and IR Excore Nuclear Instruments should not be relied upon as the only indicacion of core power. Thermocouple Maps, Loop AT's, and Incore Flux Maps should be used to verify power level.
2.9 RCS boron concentration and control bank D
/ position have been adjusted to establish a cero moderator temperature coefficient.
2.10 The RCS and Pressurirer boron concentrations
/ are within 50 ppn.
2.11 The Reactivity Computer is operable and is
/ capable of recording core power, reactivity, COLD and T HOT
- 2.12 Temporary Instrumentation has been installed
/ as required by Appendix 3 of this procedure.
( - 2.13 The computer trend printer is set up to
/ monitor the parameters specified in Appendix C ;
of this procedure. j 2.14 All' test aquipment to be used during the
/ performance of this procedure is operational and in calibration, as verified on the Test Equipment Record, Data Sheet 1 of this procedure. !
2.15 The shift supervisor has been notified of the
/ impending performance of this procedure.
2.16 Prior to commencing this test, record the
/ following information (as applicable) on each recorder strip chart.
, Test Procedure Number Recorder Number Time and Date Chart Speed Scale of each Pen Input to each Pen 4
/
I 501-7-005 I 1
, s e
3.0 Precautions and Limitations
{
3.1 A controlled Cooldown while maintaining the Reactor Critical requires careful coordination between Control Rod Position, Cooldown Rate and l Boron Concentration. A low absolute value of moderator coefficient is expected, however the operator must remain alert to the possible effects of a changing moderator temperature coefficient polarity.
3.2 During this test do not exceed 5% Reactor Power.
Caution should be used in maintaining the desired power level because of flux shadowing of the excore detectors. All possible means of determining core power should be used. Do not rely on excore detectors to provide the only indications of core power.
3.3 Control Bank D should be maintained above approximatelf 160 steps, if possible, to minimize the effects of red shadowing on the excore detectors.
3.4 The operational Safety criteria is to be prominently displayed in the control room. During the performance of this test, operation will be in accordance with the guidelines presented in the Operational 7
- s. Safety Criteria, Appendix A.
i 3.5 Do not exceed a primary to secondary differential pressure of.1600 psi.
3.6 The Reactor Coolarit System Heatup and Cooldown .
Rates should be limited to 50*F/ER.
3.7 Anvtime speed is changed on any recorder; initials, time, date and speed should be listed on the recorder chart.
l 4.0 Instructions 4.1 Determine the wide range Loop aT correction
/ factors using Data Sheet 2 of this procedure.
4.2 Record the initial plant conditions on Data
/ Sheet 3 of this procedure.
l 3 Rev. 0
1
- 501-7-005 l
.- l l
NOTE -l It is preferred that plant conditions (as specified in the Initial conditions section
! of this procedure) be maintained as close to steady state as possible prior to continuing with this test.
I l
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4.3 Perform the first Primary Calorimetric using '
l
/ Data Sheet 6 of this procedure. Simultaneously perform the first core power determa.nauen us2.ng I Appendix E of this procedure.
l 4.4 Verify that the Reactor Makeup System is
_/ capable of providing sufficient water and/or Boric Acid to compensate for coolant contraction during RCS cooldown.
l
- r. NOTE l
(. .
i Depending on Control Bank D position, and the magnitude and polarity of the moderator temperature coefficient, dilution or boration may be required.
4.5 Verify that FCV-122 is in AUTO such that a 1
/ relatively constant Pressuri=er level will be !
, maintained during cooldown. )
4.6 If it is anticipated that the S/G Atmospheric
/ Relief valves might be used for cooldown, complete FNP-2-RCP-385, " Radiological Control for Planned Operation of Main Steam Power Operated Relief Valves."
4.7 Record the time on the recorder charts in
/ the instrument rack area and/or control rocm, and start the recorders at an appropriate speed determined by the Test Supervisor.
1 v !
l l
4 Rev. O
501-7-005 4.8 Begin recording on the Reactivity Computer.
4.9 Start the computer trend printer.
/
4.10 Record initial excore detector data on Data
/ Sheet 4 of this procedure.
4.11 Record initial incore detector data on Data
/ Sheet 5 of this procedure.
4.12 Obtain an incere thermocouple map.
/ _
4.13 Initiate RCS cooldown .J.th the Steam Dump,
/ as follows:
NOTE If the S/G Atmospheric Reliefs are to be used for the cooldown, proceed to Step 4.14.
4.13.1 Place the Steam Pressure Controller in
/ MANUAL.
4.13.2 Using the Steam Pressure Controller,
/ adjust the positions of Steam Dump valves "A" and "E" to establish a RCS cooldown rate.
CAUTION Technical Specifications limits RCS cooldown rate to a maximum of 100*F in any one hour period.
The PLS document suggests that cooldown rate be limited to 50*F per hour, or less.
'W 5 Rev. 0- - . ,
501-7-005 4.13.3 approaches 543*F place and
/ AsholdT'E8th Steam Dump Interlock switches in the BY? ASS INTERLOCK position. When the " Steam Dump Train A or B Bypassd status light on the Bypass and Permissive status panel comes ON, release the switches. The Steam Dump valves should remain throttled and RCS cooldown should continue.
4.13.4 Adjust Auxiliary Feedwater flow rate to
/ maintain S/G levels at approximately 33%.
CAUTION variations in AW flow will affect RCS cooldown rate.
Re-adjustment of the Steam Dump position may be necessary.
i- 4.13.5 Use the Control Rods and/or Boric I
/ Acid concentration changes to maintain I core power at approximately 3%.
4.14 Initiate RCS cooldown with the S/G Atmospheric l
/ Relief valves, as follows:
4.14.1 Verify that the necessary radiological
/ controls are met by completion of FNP-2-RCP-388 4.14.2 Adjust the S/G Atmospheric Relief
/ valve controllers in AUTO or MANUAL to establish a RCS cooldown rate.
CAUTION Technical Specification limits RCS cooldown rate to a maximum of 100*F in any one hour period.
The PLS document suggests that cooldown rate be limited to 50*F per hour, or less.
6 Rev. 0
501-7-005 4.14.3 Adjust Auxiliary Feedwater flow rate
/ to maintain S/G levels at approximately 33%.
CAUTION Variations in AFW flow rate will affect RCS cooldown rate.
Re-adjustment of the 3/G Atmos-pheric Relief valves may be necessary.
, 4.14.4 Monitor all three RCS loop temperatures
/ and all three S/G pressures frequently to insure uniform RCS cooldown.
4.14.5 Use the Control Rods and/or Boric
/ Acid Concentration changes to maintain core power at approximately 3%.
4.15 When T
/
that t$5*"has Lo Lo been T reduced Safety below 543*F, Injection verifv Steam Dump.
Interlock P-12" s658us light on the Bypass and Permissive panel comes ON. s 4.15.1 Momentarily place both Steam Line
/ Isolation Block-Reset switches in the BLOCK position.
4.15.2 Verify that the " Steam Line Isolation
/ Train A Blocked" and " Train B Blocked" status lights on the Bypass and Permissive panel both come ON.
CAUTION If T increases above 543*i, P-12^3fl1 automatically reset.
The above steps will have to be repeated in order to block the Steam Line Isolation.
7 Rev. O
501-7-005 4.16 Verify that Charging flow remains adequate
/ to compensate for coolant contraction.
4.17 Verify that the Makeup System is maintaining
/ VCT leveel in the normal operating range.
4.18 Verily that the Pressurizer Pressure Control
/ System automatically maintains pressure at approximately 2235 psig.
4.19 When T reaches 540*F, adjust the Steam
/ Dump o$Y$/G Atmospheric Reliefs to stabilire ave' 4.19.1 Obtain the 540 F data required by
/ the following Data Sheets and Appendix:
. Data Sheet 4 Data Sheet 5 Data Sheet 6 Appencix E 4.19.2 Obtain an incore Thermocouple Map.
/
4.19.3 Record the time on the recorder charts
, / in the instrument rack area and/or G control room. .
4.19.4 When data recording.is completed
/ and after all required calculations are done, continue the cooldown while maintaining core power at approximately 3%.
4.20 When T reaches 530*F, adjust the Steam
/ Dump o3VI/G Atmosphenc Reliefs to stabilire T ay ,. j 4.20.1 Obtain the 530*F data required by the )
/ following Data Sheets and Appendix: j Data Sheet 4 Data Sheet 5 1 Data Sheet 6 Appendix E 4.20.2 Obtain an incore Thermocouple Map.
l l 4.20.3 Record the time on the recorder charts l
/ in the instrument rack area and/or !
control room.
a e.
8 Rev. 0
501-7-005 e
4 4.20.4 When data recording is completed
/ and after all required calculations are done, continue the cooldown while main-taining core power at approximately 3%.
4.21 When T reaches 520*F, adjust the Steam
/ Dump ofVI/G Atmospheric Reliefs to stabilize T ,y,.
4.21.1 Obtain the 520*F data required by
/ the following Data Sheets and Appendix:
Data Sheet 4 Data Sheet 5 Data Sheet 6 Appendix E 4.21.2 Obtain an incore Thermocouple Map.
/
4.21.3 Record the time on the recorder charts
/ in the instrument rack area and/or control room.
4.21.4 When data recording is completed
/ and after all required calculations are done, continue the cocidown while main-
._. t mining core power at approximately 3%.
s 4.22 When T reaches 510*F, adjust the Steam Dump o$Y$/G Atmospheric Reliefs to stabilize
/
T,y,.
4.22.1 Obtain the 510*F data required by the
/ following Data Sheets and Appendix:
Data Sheet 4 Data Sheet 5 Data Sheel. 6 Appendix E 4.22.2 Obtain an incere Thermocouple Map.
/
4.22.3 Record the time on the recorder charts
/ in the instrument rack area and/or Control room.
4.22.4 When data recording is completed
/ and after all required calculations are done, continue the cooldown while main-taining core power at approximately 3%.
9 Rev. O
501-7-005 e
CAUTION Control the cooldown care-fully as T approaches 500*F.
Do not exc8E8 a primary to secondary differential pressure of 1600 psi.
4.23 When T reaches 500*F, adjust the Steam
/ Dump ofY$/G Atmospheric Reliefs to stabilize T 3y,.
4.23.1 Obtain the 500*F data required ?y the
/ following Data Sheets and Appendix:
Data Sheet 4 Data Sheet 5 '
Data Sheet 6 Appendix E 4.23.2 Obtain an incere Thermocouple Map.
/ ,
1 4.23.3 Record the time on the recorder charts i
/ in the instrument rack area and/or 1 control room.
4.23.4 When data recording is completed and
/ after all required calculations are done, proceed to Step 4.24.
4.24 is being maintained at 500 F,
/ While performT"I53e following steps:
4.24.1 Obtain the ind tial 500*F heatup data
/ required by the following Data Sheets and Appendix:
Data Sheet 6 Data Sheet 7 Data Sheet 8 Appendix E 4.24.2 Obtain an incere Thermoccuple Map.
/
4.24.3 Record the time on the recorder charts
/ in the instraent rack area and/or control room.
10 -_ _ _ _ _ _ -
Rev. 0
501-7-005 l 4.24.4 When data recording is completed,
/ and after all required calculations are done, proceed to Step 4.25.
4.25 While maintaining core power at approximately
/ 3%, adjust the Steam Dump or the S/G Atmospheric Relief valves to begin a gradual RCS Heatup.
1
)
CAUTION i Technical Specifications Limits j RCS Heatup Rate to a maximum of 100*F in any one hour period.
4.25.1 Use the Control Rods and/or Boric
/ Acid Concentration changes to maintain core power at approximately 3%.
4.26 Verify that the Pressurizer Pressure Control
/ System automatically maintains Pressure at approximately 2235 psig.
4.27 When T reaches 510*F, adjust the Steam
/ Dump ofVS/G Atmospheric Reliefs to stabilize T ay,.
4.27.1 Obtain the 510*F data required by the
/ following Data Sheets and Appendix:
Data Sheet 6 Data Sheet 7 Data Sheet 8 Appendix E-4.27.2 Obtain an incere Thermocouple Map.
/
4.27.3 Record the time on the recorder charts
/ in the instrument rack area and/or control !
room.
4.27.4 When data recording is completed
/ and after all required calculations are done, continue the heatup while maintaining core power at approximately 3%.
11 Rev. O
501-7-005 4.28 When T reaches 590*F, adjust the Steam
/ Dump ofVI/G Atmospheric Reliefs to stabilize T ave' 4.28.1 Obtain the 520*F data required by the
/ following Data Sheets and Appendix: )
l Data Sheet 6 1 Data Sheet 7 l I
Data Sheet 8 Appendix E l 4.28.2 Obtain an incere Thermocouple Map.
/
4.28.3 Record the time on the recorder charts
/ in the instrument rack area and/or l control room.
4.28.4 When data recording is completed and
_f _ after all required calculations are done, continua the heatup while maintaining core power at approximately 3%.
4.29 When T reaches 530*F, adjust the Steam
/ Dump ofVI/G Atmospher:.c Reliefs to stabilize
( T,y,. .
4.29.1 Obtain the 530*F data required by the
/ following Data Sheets and Appendix:
Data Sheet 6 ,
l Data Sheet 7 Data Sheet 8 Appendix E j 4.29.2 Obtain an incere Thermoccuple Map. ;
/ l l
4.29.3 Record the time on the recorder charts i
/ in the instrument rack area and/or control room.
4.29.4 When data recording is completed
/ and after all required calculations are done, continue the heatup while maintaining core power at approximately 3%.
4.30 When T reaches 540*F, adjust the Steam
/ Dump ofVI/G Atmospher:.c Reliefs to stabilire T,y,.
J l 12 Rev. O
501-7-005 l 4.30.1 Obtain the 54C " data required by the <
~
/ following Data ,ets and Appendix:
Data Sheet 6 Data Sheet 7 Data Sheet 8 Appendix E 4.30.2 Obtain an incore Thernoccuple Map.
/
4.30.3 Record the time on the recorder charts
/ in the instrument rack area and/or control room.
4.30.4 When data recording is completed and
/ after all required calculations are done, continue the heatup while main-taining core power at approximately 3%.
NOTE As T approaches 547*F the SteadV6mp cm be need M
_. AUTO with a setpoint of 1005 psig.
4.31 When T reaches 547*F, adjust the Steam
/ Dump o$YI/G Atmospher:.c Reliefs to stabilize m
" ave
- 1 1
4.31.1 Cbtain the 547*F data required by the !
/ following Data Sheets and Appendix:
Data Sheet 6 Data Sheet 7 Data Sheet 8 Appendix E l
4.31.2 Obtain an incere Thermoccuple Map.
/
4.31.3 Record the time on the recorder charts
/ in the instrument rack area and/or control room.
4.31.4 When data recording is completed and after all required calculations are done, proceed to Step 4.32.
1 i
l l
13 Rev. O I
501-7-005 f
4.32 When the Test Supervisor determines, based <
/ on the data collected, that the test can be terminated, perform the following steps:
4.32.1 Record the time on the recorder
/ charts and stop all recorders and trend printers.
4.32.2 Shutdown the Reactor, unless operation
/ is to be continued for other tests.
4.32.3 Notify the Shift Supervisor that
/ this test is completed.
4.32.4 Attach the printouts and charts from
/ the recorders and trend printer to this procedure.
4.33 Data Reduction should be performed, as foliows:
4.33.1 Use both the cooldown and heatup data.
If for some reason the data was not obtained at exactly the required temperature plateaus mark through that temperature on the respective data sheet and record the actual measurement temperature.
4.33.2 Excore data: Sum the top and the bottom currents for each detector at each temperature plateau and enter under the sum column. The excore channel with !
the reactivity computer hooked up will l
.be read as Keithly Amplifier output and i entered in the sum column. Transfer data to Data Sheets 9 and 10.
4.33.3 Incore flux Tracing: Transfer the calculated power level at each tempera-ture plateau to Data Sheets 9 and 10.
4.33.4 Primary Calorimetric: Transfer the power level calculated in Data Sheet 6 to Data Sheets 9 and 10.
4.33.5 Average Power (Data Sheets 9 and 10):
Using the incere data and -de primary calorimetric data determine the actual core power at each temperature plateau.
A straight average should be used. l 4.33.6 Power Normalization to Reference Average Power (Data Sheet 9):
- Divide tne average power cotained at each l l
temperature plateau by the average power obtained at 550*F to correct the excore outputs.
u w
501-7-005 ,
1 1
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i I 4.33.7 Power Corrected Excore Currents and <
~
Keithly Amp Output: Divide the measured excore detector currents by the Power Normalization factor. This in effect corrects all data for fluctuations in core power. The resulting currents then will only be a function of the cold leg l
temperature.
4.33.8 Excore Current Multiplier as a function of cold leg temperature:
Divide the power corrected excore currents obtained at each temperature plateau into the excore current obtained at reference conditions.
NOTE The factors should increase )
as T decreases. Plot the !
correction factors as a .
function of T for each I detector. Th8 plots will
, be used in the Natural l
. Circulation cooldown testing program.
5.0 Acceptance Criteria 5.1 Excore detector indicated power correction
/ factors have been determined as a function of cold leg temperature for temperatures from 547'F to 500*F.
i 6.0 References 6.1 PLS Document 6.2 Farley Unit 2 Technical Specifications 6.3 VEPCO North Anna Unit 2 Procedure 2-ST-7 6.4 Westinghouse Safety Evaluation for Farley Unit 2 w' Natural Circulation Testing.
te avw e
501-7-005 7.0 Data Sheets Appendices, and Attachments e 501-7-005 Data Sheet 1:, TEST EQUIPMENT RECORD 501-7-005 Data Sheet 2:' WIDE RANGE.4T CORRECTION 501-7-005 Data Sheet 3: IRITIAL PLANT CCNDITIONS 501-7-005 Data Sheet 4: EXCCRE DATA Sw:;rx-COOLDOWN 501-7-005 Data Sheet 5: LOW POWER FLUX MAP DATA-COOLDOWN 501-7-005 Data Sheet 6: PRIMARY CALORIMIC 501-7-005 Data Sheet 7: EXCORE DATA S m T-EEATUP 501-7-005 Data Sheet 8: LOW POWER FLUX MAP DATA-EEATUP 501-7-005 Data Sheet 9: NI CORRECTION FACTOR CALCULATION-CCOLDOWN 501-7-005 Data Sheet 10: NI CORRECTION FACTOR CALCULATION-EEATUP 501-7-005 Appendix A: OPERATIONAL SAFETY CRITERIA
,e 501-7-005 Appendix 3: TEMPORARY RECORDERS 501-7-005 Appendix C: PROCESS COMPUTER TREND BLOCKS 561-7-005 Appendix D: PRIMARY CALORIMETRIC RE. M CE DATA 501-7-005 Appendix E: CORE POWER DETERMINATION 16 Rev. O
501-7-005 Data Shoot 1
- Rcvision 0
. Page 1 of 1 DATA SEEET 1 TEST EQUI? MENT RECORD TEST EQUIPMENT
1 1
i I
- This applies only to temporarily installed test equipment or instrumentation. Permanent instrumentation which is part of the system and shown on drawings, should not be included.
s Test Supervisor /
Signature Date
501-7-005 Data Sh9Gt 2 Revision 0 l
. Page 1 of 2 l DATA SHEET 2 WIDE RANGE AT CORRECTION LOOP A Item Parameter Location Reading Parameter No. Rack / Test Point Volts (1) F (2) i Loop A 1 Hot Leg Loop A 2 Cold Leg 1
Loop A 3 W. R. AT Item 1-Item 2 = *F Loop A I 4 N. R. AT W. R. AT 5 Correction Factor (C.F.) = Item 4-Item 3 = *F (37 LCOP 3 Loop B 1 Hot Leg Loop B 2 Cold Leg Loop B 3 W. R. AT Item 1-Item 2 = *F Loop B 4 N. R. AT W. R. AT 5 Correction Factor (C.F.) = Item 4-Item 3 = *F (3I
501-7-005 Data Shoot 2 Rcvision 0 i
LOOP C Loop C 1 Hot Leg l
Loop C 2 Cold Leg Loop C 3 W. R. AT Item 1-Item 2 = F Loop C 4 N. R. AT W. R. AT ,
5 Correction Factor (C.F.) = Item 4-Item 3 =
- F (3{
(1) Using a Digital Voltmeter, measure thc voltage au the specified test points as rapidly as possible.
l (2) Detarmined by converting voltage reading to *F.
(3) The correction factor (C. F.) determined in item 5 is used on Data Sheet 6 to correct the calculated wide range AT for the AI across the core generated by the Reactor Coolant Pumps. l l
i 1
,-n - ,.
7--m7
501-7-005
. Data Shcat 3
. Rcvision 0 l Page 1 of 2 DATA S E 3 -
INITIAL PLANT CCNDITIONS - STEADY STATE REACTOR CCOLANT SYSTEM Pressurizer Pressure PR-444 (Red Pen) psig I
Pressuriser Level LR-459 (Red Pen) % '
i RCS Loop 1 Hot Leg Temperature TR-413 (Red Pen) "F RCS Loop 1 Cold Leg Temperature TR-410 (Red Pen) *F RCS Loop 2 Hot Leg Temperature TR-413 (Blue Pen) *F RCS Loop 2 Cold Leg Temperature TR-410 (Blue Pen) *F RCS Loop 3 Hot Leg Temperature TR-413 (Green Pen) *F RCS Loop 3 Cold Leg Temperature TR-410 (Green Pen) *F
\
Reactor Coolant Loop 2A T,yg TI-412D *F Reactor Coolant Loop 2B T avg TI-422D *F Reactor Coolant Loop 2C T avg TI-432D *F Reactor Coolant Loop 2A AT TI-412A %
Reactor Coolant Loop 23 AT TI-422A %
Reactor Coolant Loop 2C AT TI-432A %
STEAM GENERATORS Steam Generator 2A Level (NR) LI-474 %
Steam Generator 23 Level (NR) LI-484 %
v a' Steam Generator 2C Level (NR) LI-494
501-7-005 Dcta Shnst 3
.' Ravision 0 Page 2 of 2 9
l Steam Generator 1 Level (WR) LR-477 Pen 1 (Red) %
Steam Generator 2 Level (WR) LR-477 Pen 2 (Green) %
Steam Generator 3 Level (WR) LR-477 Pen 3 (Blue) %
Steam Generator 2A Pressure PI-474 psig Steam Generator 2B' Pressure PI-484 psig Steam Generator 2C Pressure PI-494 psig 0
Steam Generator 2A Feedwater Flow FI-476 x 10 #/hr.
0 Steam Generator 23 Feedwater Flow FI-486 x 10 #/hr.
6 Steam Generator 2C Feedwater Flow FI-496 x 10 #/hr.
6 Steam Generator 2A Steam Flow FI-474 x 10 lbs/hr.
6 Steam Generator 23 Steam Flow FI-484 x 10 lbs/hr.
6 Steam Generator 2C Steam Flow FI-494. z 10 lbs/hr.
REACTOR POWER NIS channel N-41 %
NIS Channel N-42 %
NIS Channel N-43 %
NIS Channel N-44 %
NIS Charnel NI-35 amps NIS channel NI-36 amps NOTE l
Attach a copy of the computer printout of the Incore Thermocouple Temperature
- Map.
Data Taken By:
Date:
, 501-77 ' }S , ,
Data Act 4 ' -
Revicion 0 -
Page 1 ofl .
DATA SHEET 4 EXCORE DATA SHEET - COOLDOWN Shutdown Bank Position: A B D0to Control Bank Position: A B C D Pow 3r N-41 N-42 N-43 N-44 Pirn/ Temp Top Bot *'om Sum Top Bottom Sum Top Botton Sum Top Bottom Sum
/547
/540_ .
/S30
/520
/510
/500 NOTE: One of the PR Channels will be connected to the Reactivity Computer. Record Keithly Amplifier output for that channel, above.
COMMENTS:
Data Taken By:
Date:
n --
'- S01-7-005 , ,
Data Shent Rnvision 0 Page 1 of 1 .
DATA SHEET 5 LOW POWER FLUX MAP DATA - COOLDOWN Initial Final RCC Bank /RCCA Positions (steps)
Mrp No.: SDA SDB RCS T,yg (*F):
Dato: IR-35 (amps): CBA CBB CBC CBD Unit IR-36 (amps):
Time Calculated Control of Detector-Core Location Detector-Range Power P-250 Bank RECORD A B C D E A B C D E Level UO906 Position S47 S40 S30
$20
$10 S00 ,
NOTE: Refer to FNP-2-SOP-44.0 for operation of the Incore Movable Detector System.
Detector A B C D E Remarks:
Detector voltage Recorder Pot.
Data Taken By: Date:
0
501-7-005 Dsta Sh:2t 6
" R; vision 0 Page 1 of 4 .
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DATA SEET 6 PRIMARY CALORIMETRIC Loco A - Coold..m
- 1 #2 #3 #4 d5 46 #7 48
\pprox. HL CL T Loop Loop Flow Loop Rx PW
.iCS Temp #2-#3 #4+c.f.(3) #5xCp(g) 96 x #7
'F Volts *F(1) Volts
- F'1) *F 'F Btu /lb 10 f4)lb/hr 10 Stu/hr 547 (REF) 540 530 520 __
510 500 Loop A - Heatuo r
L 310 1
520 530
'540 547 i
(1) Using a Digital Voltmeter, measure the voltage as rapidly as possible.
Convert the voltage reading to *F using the appropriate scaling.
(2) From Data Sheet 2.
(3) Cp from Appendix D. Remar'ss :
(4) i from Appendix D.
Jar by:
03 t+3. ,
501-7-005 Data Sh st 6
- R; vision 0 Page 2 of 4 DATA SHEET 6 PRDfARY CALORDfETRIC Loop B - Cooldown
, 19 110 #11 #12 #13 #14 415 116 epprtx. EL CL T L p Flow Loop Rx Pw
- 10-#11 #12+c.f.(2) L EY3)
- 13xCp WCS Temp f4)lb/hr #1gx#15 i SF Volts *F(1) Volts *F(1) *F *F Btu /lb 10 10 Btu /hr i
347 (REF) ,
340 530 520 510 500 Loop 3 - Heatuo i
5r A
l 510 l
520 I
530 l
540 I
547 -
Remarks:
Data by:
Dnts:
)
. 501-7-005 Dsts Sh::t 6 R; vision 0 Page 3 of 4 _
DATA SHEET 6 PRIMARY CALORIMETRIC Loco C - Cooldown 417 #18 419 420 #21 #22 #23 424 tpprox. HL CL T L P
- 21xCp(3)
L P 1W L P RX Pm RCS Temp #18-919 #20+c.f.(2) fA) #23 x #24
'T Volts *F(1) Volts *F( ) *F *F Btu /lb 10 lb/hr 10 Btu /hr is7 (REF)
%c
$30 320 510 l$00 l
Loop C - Heatuo
$ (~
510 520 530 S40
$47 i
l l
l Remarks:
Dsts by:
Date:
r
501-7-005 Data Shcot 6 R vision 0 Page 4 of 4 C
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DATA SHEET 6 PRIMARY CALCRIMETRIC Total - Cooldown
)25 #26 r)27 :)28
.pprox. Total Reactor Power Reactor Power % Reactor Power
'.CS Temp 18+g16+124 #26 x 0.29307 127 X 0.02932
- Y 10 Btu /hr MWt %
147 (RET) 540 i30 320 ilo 500 Total- Heatuo 5r
. 1 1
310 J l
320 330 340 547 l
Remark 2:
Data by:
Dnta:
v'
' ("- S01-7, ')S ,
Data 5 et 7 * -
Revispe 0 -
Page 1 uf 1 ,
DATA SilEET 7 EXCORE DATA SilEET - IIEATUP Sliutdown Bank Position: A B Date Control Bank Position: A B C D
- Power N-41 N-42 N-43 N-44 Tire / Temp Top Bottom Sum Top Bottom Sum Top Bottom Sum Top Bottom Sum
/500
/ Slo
/520
/S30
/540
/547 NOTE: One of tlie PR Cllannels will be connected to tile Raactivity Computer. Record Keittily Amplifier output for tlidt clnannel, above.
- COMMENTS:
Data Taken By:
Date:
n.
i f 501-7-005 , ,
Data Sheet Revision 0 Page 1 of 1 -
DATA SilEET 8 LOW POWER FLUX MAP DATA - IIEATUP Initial Final RCC Bank /RCCA Positions (steps)
Map No.: SDA SDB RCS T,yg ( F):
Date: IR-35 (amps): CBA CbB CBC CBD UniL: IR-36 (amps):
Time Calculated Control of Detector-Core Location Detector-Range Power P-250 Bank RECORD A B C D E A B C D E Level UO906 Position _
500 _
$10
$20 S30 . _ _
$40
'ia7 NOTE: Refer to FNP-2-SOL)-44.0 for operation of the Incore Movable Detector System.
Detector A B C D E Remarks:
Detector voltage Recorder Pot.
Data Taken By: _.
Date: ,
- - - ---____________ __. n_____--_________4
501-7-005
. Data Shoot 9 Rsvision 0 Page 1 of 1 ~
DATA SEEET 9 NI CORRECTION FACTOR CALCULATION - CCOLDOWN l 547 540 53C 520 510 50C APPROXIMATE AVERAGE COLD LEG TEMPERATURES (*F): REF.
Item 4 Parameters i Movable Detector i 1 (% RTP)
Primary Calorimetric 2 (% RTP) _
Average Power 3 (% RTP)
Power Normalization 4 to REF condition 1.00 Excore Currents N-5 and N-Keithly Amp N-Outuut KA Power Corrected N-(."
Excore Current.:: N-6 & Keithly Amp N-Outuut KA N- 1.00 ,
l 7 Correction N- 1.00 l Factors N- 1.00 KA 1.00
,Remarlu:
Completed By:
1 Date: !
l
' l l
t - , _ _ - ___ , _ _ . __ . _ , . _ _ _ . - _ _ _ ._. - _ . _ _ . _ _ _ _ _ - _ .
501-7-005 Data Shoot 10
'- Rcvision 0 Page 1 of 1 l DATA S N 10 ~l NI CORRECTION FACTOR CALCULATION - EEATUP l 500 510 520 530 540 547 l APPROXIMATE AVERAGE COLD LEG TEMPERATURES
('F): REF.
iItem 4 Parameters Movable Detector '
1 (% RTP)
Primary Calor 113tric 2 (% RTP)
Average Power 3 (% RTP)
Power Normalization 4 to REF condition _
1.00 Excore Currents N-5 and N-Keithly Amp N-l Outuut KA Power Corrected N-b- Excore Currents N- -
6 & Keithly Amp N- -
Out=ut KA N- 1.00 7 Correction _N-- 1.00 Factors N- 1.00
(
KA 1.00 1
l Remarks:
1 l
Completed By: l Date:
l
. 501-7-005
, . . Appcndix A Rcvision 0 Page 1 of 2 APPENDIX A OPERATIONAL SAFE"rY CRITERIA During the performance of these tests, plant operations will be controlled or limited by the following set of criteria for operation.
- 1. Operational Guidelines (for all Tests)
- a. Primary System Subcooling (T sat Margin) (later)
- b. Steam Generator Water Level ~ 33 percent
- c. Pressurizer Water Level (1) With RCP's runni ng > 22 percent Span (2) Natural Circulation > Value when RC?'s
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are tripped
- d. Loop AT (later)
- e. T ave (later)
- f. Core Exit Temperature (highest) (later)
- g. Power Range Neutron Flux < 5 percent Reactor Power
- h. Control Bank D (later)
- 2. Reactor Trip and Test termination must occur if any of the following. limits are reached.
- a. Primary System Subcooling (T sat Marg n) (later)
- b. Steam Generator Water Level <5 percent Narrow Range Span
- c. NIS Power Range, 2 Channels >7 percent l Reactor Power
- d. Pressurirer Water Level < 17 cercent Scan
'or an unehlained
~
decrease of more than (later) percent not I concurrent I with a T ava change -
501-7-005
,, . AppOndix A
- Rcvision 0
. Page 2 of 2
- e. Any Loop aT (later)
C. T (later) ave
- g. Core Exit Temperature (later)
- h. Uncontrolled Rod Motion (later)
- 3. Safety Injection must be manually initiated if any of the following limits are reached.
- a. Primary System Subcooling (T sat Margin) (later)
- b. Steam Generator Water Level <0 percent Narrow Range Span or Equivalent Wide Range level
- c. Containment Pressure (later) r -
- d. Pressurizer Water Level < 10 percent Span
- or an unex-plained decrease of more than 10 percent not concurrent with a T"V9 change.
- e. Pressurizer Pressure Decreasen by,200 psi or mcre in an unexplained manner.
NOTE Safety Injection termination will be in accordance with the termination criteria set forth in FNP-2-EOP-0.
l O
501-7-005
. . . . Appendix B
- Rnvielon 0
- Page 1 of 3
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APPENDIX B <
TEMPORARY RECORDERS Connnct temporary strip-chart recorders as indicated belcw.
1.0 Reactivity-Computer Recorder
- a. Flux
- b. Average wide range T COLD
- c. Average wide range T EOT
- d. Reactivity 2.0 Stripe Chart Recorder No. 1 Channal Connection Monitoring FP-4143, C1-432 RCS Flow, Loop 1
{.
2 FP-424B, Cl-433 RCS Flow, Loop 2 3 FP-4343, C1-434 RCS Flow, Loop 3 4 PP-455F, Cl-428 Pressuriser Pressure 5 LP-4593, Cl-442 Pressurizar Level 3.0 Strip Chart Recorder No. 2 Channel Connection Monitorinc 1 PP-474D, C2-443 S/G No. 1 Pressure 2 LP-474B, C1-429 S/G No. 1 Level 3 FP-4743, C3-741 S/G No. 1 Steam Flow 4 PP-484B, C2-444 S/G No. 2 Pressure
501-7-005
, . . . . AppOndix B
- - Rnvision 0 Page 2 of 3 4.) Strip-Chart Recorder No. 3 e Cuaanni Connection Monitoring 1 PP-494B, C2-445 S/G No. 3 Pressure 2 LP-494B, Cl-431 S/G No. 3 Level 3 FP-4943, C3-748 S/G No. 3 Steam Flow 4 FQ-3229A, CJ-234, Pins 21 & 22 S/G No. 1 Aux Feed Flow 5 FQ-3229B, CJ-234, Pins 29 & 30 S/G No. 2 Aux Feed Flow 6 FQ-3229C, CJ-234, Pins 33 & 34 S/G No. 3 Aux Feed Flow 5.0 Strip-Chart Recorder No. 4 (optional) iChannni Connection Monitoring 1 FQY-122, C6-522 RCS Charging Flow 2 FQY-150, C6-433 RCS Letdown Flow
?(~ -
3 PP-403B, C4-433 Wide Range RCS Pressure 4 TD-454, C6-636 Pressurizer Steam Temp.
5 TD-453, C6-636 Pressurizer Liquid Temp.
'A .*
. 501-7-005 l
- Appandix B l Rnvicion 0 '
Page 3 of 3 6.0 Strip-Chart Recorder No. 5
- Cnannni Connection Monitorina 1 TP-413A, Cl-435 Wide Range TECT L 91 2 TP-410A, C2-435 Wide Range T COLD b E1
, 3 TP-423A, C1-436 Wide Range TECT L P2 4 TP-420A, C2-436 Wide Range T COLD L P2 5 TP-433A, Cl-441 Wide Range T ECT L p3 6 TP-430A, C2-441 Wide Range T COLD Loop 3 The above installation has been completed and check-out is satisfactory.
Completed by: /
Signature Date Test Supervisor /
( Signature Date The above installation has been removed.
Completed by: /
Signature Date J Test Supervisor / (
Signature Date
501-7-005
., ,,' , Appendix C
. Rcvision 0
- Page 1 of 2 APPENDIX C e PROCESS CCMPUTER TREND BLCCK A COLUMNS ADDRESS PARAMETER UNITS 1 T0406A RCL A T COLD 2 T0426A RCL B T COLD 3 T0446A RCL C T COLD 4 T0419A RCL A THOT F 5 T0439A RCL B THOT F 6 T0459A RCL C THOT 7 T0400A Tgyg MCP A *F 8 T0420A Tgyg MOP B 'F 9 T0440A Tgyg MOP C *F 10 T0403A AT LOOP A %
_- 11 T0423A AT LCOP B %
12 T0443A AT LCOP C %
13 F0128A~ CHARGING FLOW GPM 14 F0134A LETDCWN FLOW GPM 15 U1250 EIGHEST REL FUEL ASSY PWR 16 LO480A PRESSURI M LEVEL %
17 LO112A VCT LEVEL %
18 U1251 EIGHEST REL ASSY PWR INDENT
501-7-005
.'..'"' APP 9ndix C Revision 0 Page 2 of 2 ,
- PROCESS COMPUTER TREND BLOCK 3 l
COLUMNS ADDRESS PARAMETER UNITS 1 LO400A S/G A LEVEL %
l 2 LO420A S/G B LEVEL %
l 3 LO440A S/G C LEVEL %
4 PO400A S/G A PRESS PSIG S PO420A S/G B PRESS PSIG 6 PO440A S/G C PRESS PSIG 7 PO483A PRESSURIZER P PSIG 8 PO499A RC SYSTEM P PSIG 9 P0142A CHARGING PRESS PSIG 10 UO482 AVG PZR PRESS PSIG 11 UO483 AVG PZR LEVEL %
12 U1118 RX THERMAL PCWER MW 13 U1170 AVG T/C TEMP *F
501-7-005
, . . , - Appgndix D RGvision 0 Page 1 of 1 APPENDIX D PRIMARY CALORIMETRIC RE E NCE DATA Temp. Cp I1) i
- F Btu /lb. *F lbm/br.
560 1.270 (later) 550 (REF) 1.246 (later) 540 1.221 (later) 530 1.202 (later) 520 1.183 (later) 510 1.168 (later) 500 1.152 (later) 490 1.140 (later) e
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(1)These values are from the 1967 ASME Steam Tables.
Values are for a pressure of 2250 psia.
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, 501-7-005 )
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- App 3ndix E i Revision 0 l Page 1 of 1 APPENDIX E M/D POWER DETERMINATION I
i
. l'. '~-Set up the movable detector system for a 1 pass partial
. - . . . - core flux map. Select flux thimbles as per the table ,
- -- below for the flux cap. l Detector Core Location 10-Path Position A H-11 ' ' ~ ~ ~
9
. _ _ .:: . ____ ._ _~" ~ '* "::. '.- ~
~
~
2 -- . ' ' :" ~ ^ ~
~ 10 B D-10
___.C " - - -- - --
- -- D - -
D 7
._ . . _._. . N- 5 _
_ ,_ _ ( .& *e --i These positions may be altered by the test engineer, - a based upon low-power physics testing results and >
previous special testing experience.
- 2. With all 5-path selector switches set to normal, run a flux trace while obtaining data for a Primary
. - - _ - . . -- _ calorimetric.
From the pass printout on the line printer obtain the Integral voltages for each detector.
~
5 -- -
Calculate the volts per % power as follows: y ,It fvDet.
.P . . . . . . .
.____ Where: Vp = Volts per % power ___._ _ _ _ _ _ . _ . _ . .
V Det = Integral volts of the detector.
P = % power from primary calorimetric.
- 3. For power determination, obtain a 1 pass partial care flux map. Determine the % power as follows:
5 P= 1 A Det.
Y P
Where: V Det
= Integral v its of the detector Vp = Volts per % power (previously calculated)
P = % power